ML19282C229

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Forwards Info Supplementing Re Qualification of Limitorque Valve Operator Terminations & stem-mounted Limit Switch Terminations
ML19282C229
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 03/19/1979
From: Parker W
DUKE POWER CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 7903220262
Download: ML19282C229 (60)
v • d • e


Text

{{#Wiki_filter:DUKE POWER COMI%NY l'OW E ld IJUILDING 422 NOIITil Citt:HCit STIn.E T, CHAldDTT r, N. C. ana.sa wiuim o. mnren..an. March 19, 1979 Vice Parm orNT TC t t e-ON E. Aa E

  • 7C4 S f t Ane PaoouCTiom 3 7 3-4 0 +3 3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Mr. Robert L. Baer, Chief Light Water Reactors, Branch No. 2 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370

Dear Mr. Denton:

Attached is supplemental information concerning the qualification of Limitorque valve operator terminations and stem mounted limit switch terminations. Ten copics of each attachment are included in this submittal. This information is being provided in response to a request by the Instrumenta-tion and Control Systems Branch and supplements the information contained in my October 5, 1978 letter. Very truly yours, 6 / I rdw.i G). 'a, s u.

c William O. Parker, Jr.

/2 ,, i L .(T GAC:scs Attachment %og a PROG ee,#'&g 4 / sa h a t .4 2 7903220261 ~ ~ th Anniversary %e#oWER6,$ 0

.s> DUKE POWER COMPANY McGUIRE NUCLEAR S1ATION Environmental Qualification of Safety-Related Terminations Located inside Containment The following information supplements our submittal of October 5,1978 concern-ing safety-related terminations located inside containment. Motor Operated Valve Actuators (Limitorque) As stated in our previous submittal, Limitorque valve actuator terminations consist of terminal connections for indication circuits and splices for power circuits. The spliced power connections will be sealed over with Raychem Thermofit shrinkable tubing, the qualification of which is covered in Attachment I to our previous submittal. The terminal connections for the indication circuits were qualified with the valva actuator. The qualification of the Limitorque valve actuator including the terminal connections is covered in Attachment 11. Limit Switches For clarification, it should be noted that the limit switches referred to in our previous submittal were of the stem-mounted type. All limit switches which are an integral part of the valve actuators were qualified with the actuators. For stem mounted limi t swi tches, conductors will be terminated wi thin the limit switch assembly. The cable entrance into the limit switch assembly will be sealed with a potting compound (3M Scotchcast 9 resin) to prevent intrusion of the steam environment. This potting compound has been evaluated by testing to the extreme accident temperatures and pressures postulated for McGuire. This evaluation test indicates that the potting compound will provide an effective seal. A confirmatory qualification test to meet the requirements of iEEE 323-1971 is in progress with the results expected to be available in May 1979 now

%.vg m.s Goo m LIMITORQUE CORPORATION ri;sy;2q MFitl ATED WITH PHILACELPHI A GEAR CC@C AATION f t t 181 South G ulph A c a d. Kin g of P r u s s i e. P a.19 4 0 6 p k" g Telephone (215) 265-3000 T e l e x - 8 4 - 6 3 21 -1N h h April 6, 1976 e F c. . %. ? . u. u Dtike Power Company P.O. Box 2178 bC*'T* Charlotte, N.C. 28201 1-2 S oh v w; .in Attention: Mr. Jim W. Loftin

Subject:

LIMITORQUE CORPORATION QUALIFICATION TYPE TEST REPORT FOR PRESSURIZED WATER REACTOR (PWR) Project No. E. 0 0 4 5 6 Gentlemen: We are pleased to enclose a copy of the latest Limitorque g Corporation qualification test report.for valve actuators f ar nuclear containment service. This test report is in complete accordance with the IEEE Standard 382-1972. The test was successfully performed between June 7, 1974 and November 22, 1974. To our knowledge, this was the only test report of its kind where a complete valve actuator went entirely thru all of the qualification testing as required by IEEE-382-1972. All of the actual data recorded during the entire test is on file at Limitorque Corporation, King of Prussia, Penna. ! for customer audit whenever necessary. If you have any questions concerning this, please do not hesitate to contact us or your local Limitorque representative. Very truly yours, LIMITO_RQUE CORPORATION 9 s ',j

e. >., ; -- r w.

Edward F. Lawson Sales Manager nc. cc: G. Cusack/ Charlotte Automated Verve Operators and Jacks for Industry

e \\ $1 t' C.W E NUCLEAR POWER STATION QUALIFICATION TYPE TEST REPORT LIMITORQUE VALVE ACTUATOPS FOR PWR SERVICE PROJECT #600456 Tested per IEEE Standard 382-1972

  • O Test Performed 7 June 1974 to 22 November 1974 Prepared by Limitorque Corporation Test Laboratory Prepared by Walter L. Syke/

Test En ineer l& 9 7f Date 4 A Proved P W[iefEngineer J. Denkowski Ch Date j en

5 s FNR Qualification Project #600456 /"' TABLE OF CONTENTS .h. .q - F

1. 0 *E Introduction

.................................page F-1 JF 2.0ff Identification of sample Valve Actuator......page 1 3.0 Type Test Procedure ..........................page 2 3.1 Aging Simulation 3.1.1 Thermal Aging 3.1.? Mechanical Aging 3.1.3 Radiation Aging 3.2 Seismic Qualification 3.3 Radiation Exposure %p 3.4 Accident Simulation 3.4.1 Test Description 3.4.2 Test Procedure for LOCA Test Figure 5 - Specified Accident Profile 3.5 Post Test Inspection 3.6 Post LOCA Load Cycling Test 3.7 Final Inspection 4.0 Test Results .................................page 11 4.1 Mechanical Aging 4.2 Seismic Qualification 4.3 Radiation Aging & Exposure b I

9 e PWR Qualification Project #600456 /*' TABLE OF CONTENTS (cont. ) }L &x Yg-y

4. h Accident Environmental Simulation Test Results 4.4.1 Temperature and Pressure Profile Figure 6 - Actual Accident Profile Figure 7 - 1st Transient BVR Profile Figure 8 - 2nd Transient PWR Profile 4.4.2 Chemical Spray Delivery 4.4.3 Chamber Humidity 4.4.4 Insulation Resistance Measurements Table II - Insulation Resistance of Power & Control Leads sg gas 4.+.5 Actuator Cycling Date Table III - Valve Actuator Cycling Data 4.5 Post LOCA Inspection Figure 9 - Post LOCA Conditions (pho togra r h) 4.6 Post LOCA Load Cycling 4.7 Final Inspection Results 4.7.1 Motor Inspection and Dismantling 4.7.7 Valve Actuator Inspection and Dismantling Figure 10 - Test Unit Final Inspection ( pho tograph) 5.0 Conclusion

........................................page 28 II

PWR Qualification Project #600456 (* i APPENDICES T_ b k-e- APPE,hDIX A - Reliance Electric Company's Certificate of Compliance 57' APPENDIX B - Mechanical Aging, Load Cycling and Thrust Measurements Appendix C - Certificate of Compliance from Isomedix Corporation APPENDIX D - Lockheed Environmental Labs' Seismic Report No. 3521-4911 APPENDIX E - Figure 1 - Test Chamber Figure ?- Steam Ganerator % gas Figure 3 - Control A Instrumentation Panel APPENDIX F - Figure 4 - Schematic - Instrumentation and Power System Table I - Summary of Data Acquisition System III

FWR Qualification (~ 1.0 Introduction 1 A typical Limitorque Valve Actuator, SMB-0 with'ts 40 ft-lb [ motor (SMB-0-40) was submitted for qualification to the type ~+ 7; g-test specified by IEEE std. 382- '72' for service in a Pres-surized Water Reactor (PWR) containment chamber in Nuclear Power Station application. The SMB-0-40 Valve Actuator was subjected to mechanical aging simulation to approximate 40 years service life, radiation ex-posure (Both Normal Life levels plus accumulative doses) and other environmental condisions all as indicated in IEEE Std. 382 '72'. Additional load. cycling was performed after LOCA g environmental conditions to determine the post accident abilities of the valve actuator. 2.0 Identification of Sample Valve Actuator TEST UNIT A limitorque SMB-0 Nuclear Valve Actuator with a 40 ft-lb nuclear containment motor (RH Insula tion Class) was con-structed per standard nuclear bill of materials and stan-dard nuclear motor specifications. The following inform-ation was taken from the identification tags: h 1.

FWR Qualification (" Valve Actuator Type / Size...............SMB-0 Manufacturer ......................Limitorque Corporation F }. Order Number..................... 600456-A p cr Serial Number.................... 189835 g.. + Electric Motor Information: Size............................. 40 ft-lb stall 8 ft-lb run Manufacturer...................... Reliance Electric Company Identification number............ 2Y267074AlEZ Full Load Speed.................. 1735 RPM Frequency........................ 60 Hz h Voltage.......................... 460 Volts p.s Insulation Class ..................RH Type ..............................P 3.0 Type Test Procedure The type test plan as described in IEEE Std. 382 '72', para-graph 4, consists of three basic parts:

1. Aging Simulation 2.

Seismic Qualification

3. Accident Environmental Simulation f (m.

2.

FWR Qualification ) I' ' As an added test margin, the test actuator was submitted to additional load cycling after completion of all the };. requiredenvironmentalconditionsandpriortoffnal e g. 5 inspection. This additional load cycling is not a re-g E quirement of IEEE Std. 382 '72'. A base test motor was processed with the Test Unit for additional engineering information. 3.1 Aging Simulation (IEEE Std. 382 para. 4.2) 3.1.1 Thermal Aging Thermal aging was performad on the motor stators by the motor manufacturer (Reliance Electric Com-rm pany) in cooperation with Limitorque Corporation. The motor stator was heat aged for 100 hours at o 180 C. A certificate of compliance was supplied by Reliance Electric Company verifying the thermal aging of the stator (see Appendix A.) 3.1.2 Mechanical Aging Mechanical Aging was performed on the Test Unit by the Limitorque Test Laboratory. Data on the Aging & Post test Cycling is presented in Appen-dix B. Although IEEE Std. 382- '72' requires 500 cycles, the unit was cycled thru 1208 cycles, 3.

FWR Qualification 3 ("N i each cycle consisting of one close stroke and one open stroke at room ambient conditions. The} Limit- { orque Valve Actuator was seated at the end o,f the R .S.f close stroke and the seating thrust monitored. The thrust applied was equivalent to the thrust & torque ratings of the SMB-0 actuator. A typical stroke time of 40 sec. was chosen for the actuator operat-ing time. 3.1.3 Radiation Aging (IEEE Std. 382 '72' Part II Section 1) The Aging dose of 4 Megarads was combined with the accident dose (200 Megarad) per IEEE Std. 382 '72' ,( g /"N part III and is discussed in the following section 3.3 of this report. 3.2 Seismic Qualification (IEEE Std. 382 Para. 4.3) The Seismic Qualification was performed by Lockheed Elec-tronics, Inc. Environmental Laboratory on a Reaction Vibration machine. The Test Unit with motor, was scanned in each of the three major axis over a frequency range of 9 5 to 35 Hz to search for resonance. No resonance was found. i 4.

PWR Qualification /* i The Valve Actuator was mounted on a test fixture to provide simulated valve seating loads, during>the E i dwell portions of the seismicqualifications.(The i jE load imposed was equal to the rating of the test ~. _E actuator. The vibration machine was adjusted to a displacement (0.050" D. A.) equivalent to 3 g's acceleration at a frequency of 35 Hz. The test sample was then vibrated for a period of ten (10) seconds at each even integer of frequency from 6 Hz to 34 Hz. The unit was cperated during the dwell through one cycle from open limit-to-torque switch seated. position and back to original g .s point. The vibration machine was adjusted to a dis-placement (0.100" D. A.) equivalent to 6 g's ac-celeration at a frequency of 35 Hz. The test sample was then vibrated for a period of ten (10) seconds at 35 Hz and operated during the dwell. The dwell tests above were performed in each of the three major axis. A report on the Seismic Qualifi-cation was prepared by Lockheed Electronics Corpor-ations Environmental Laboratory (Report No.3521-4811 and is presented in Appendix D.) The duration of each [ t'% stroke was 40 seconds. s.

PWR Qualification /*'

3. 3 i Radiation Exposure (IEEE Std. 382 Part II Section 1)

The Limitorque Actuator and motor were subjecte to a ~ ], Gamma Ray Irradiation of 204 Megarads per IEEE td. E g 382 '72' requirements. t The Test Unit was placed in a Cobalt-60 and Cesium-137 field of 1 Mrad / hour at an air equivalent dose. A total radiation dose cf 204 Megarads was applied after thermal aging, mechanical aging and seismic qualification. The radiation exposure was performe6 by Isomedix Corpor-ation. A Test Certification was supplied by Isomedix ) /% Corporation and is presented in Appendix C. 3.4 Accident Simulation (IEEE Std. 382 '72') 3.4.1 Test Description The test was performed at Limitorques' Environmental Test Facility, see figures 1, 2 and 3 in Appendix E. A schematic of the instrumentation system and a summary of instruments used during the test are presented in Figure 4 and Table I located in Appen-dix F. The limitorque Actuator was mounted on a thrust tube attached to the side of the test chamber with the stem thrusting against the load cell mounted 6.

PWR Qualification I i externally to the test chamber. (see Figure 1, Appendix E) {E s Y g, ? { Control and power lead connections were.hade f. [ through flexible pressure tight conduit con-nections run between the units and the access ~ ports of the test chamber. The external wire harness was run to a junction box, where ter-minal strips provided access to each lead for monitoring insulation resistance. The terminal strips were wired to a control system (see Figure 4, Appendix F). The control panel illus-Rr trated in Figure 3, (Appendix E) contains a power monitoring system to monitor line voltage, current in each of the three (3) motor legs and the power consumption of the motor. Pressure and temperature were monitored on the multipoint temperature recorder and strip chart recorder mounted on the test console (Figure 3, Appendix E). In addition to the automatic moni-t toring system,.the temperature and pressure was monitored by a pressure gauge and two thermometers mounted in the side wall of the test chamber (see Figures 1 and 4.) M D: rat p s t,. t --t . r_g c * * ^.1 % AS N w.T >_- ca lE. i: Ams :-t ac. IM D N tt. CA GQJMED TO YA O bEUN T5kE NM N E 7. Ar.icATOA T&.t Lt " We ba d LETTt C. @ M a c.c a NA. W W1% 1-13'12} 3

PWR Qualification During the rapid temperature and pressure tran-f~s sients, the chamber ambient and limit switch com-E e partment internal temperature and pressure were 1 v-monitored continuously on the strip chart re-h g-corder. Cooling coils mounted inside the chamber provided cooling capacity to reduce the temperature in the chamber to the various temperature plateaus. A double spray system provided a reliable source of chemical spray during the test profile. Flow meters mounted on the panel near the test chamber D (see Figure 1, Appendix E) monitored the chemical fluid flow. Spray nozzles mounted on two sets of manifolds (3 nozzles per manifold) with the ability to switch manifold provided the proper spray pat-tern. The pressure in each active manifold cet was monitored to indicate any restriction of the spray nozzle orifice. A back flush system was provided to back flush the spray manifold. 1 }- 3.4.2 Test Procedure for LOCA Test The Limitorque Valve Actuator was exposed to /~\\ steam and chemical spray in accordance with the 8.

PWR Qualification /** criteria listed in Table 1 in the "IEEE Guide for Type Test of Class 1 Electric Valve Operators for F j Nuclear Power Generating Stations" IEEE Std. y a 382 '72'. The temperature / pressure profile is illustrated in Figure 5, which also shows the sche-dule for measuring the insulation resistance of the power and control leads and cycling of the Limitor-que Valve Actuators. During the first four days of the test, the specified temperature and pressures were maintained by the con-tralled injection of steam into the test chamber. 3 O p During the remainder of the test, the 200 F/10 psig state was maintained by filling the test chamber with air controlled to the proper pressure and using elect-rical heaters. The atmosphere was kept saturated with water vapor by maintaining condensate in the bottom of the tank and by daily injections of steam. 3.5 Post Test Inspection A visual inspection of the limit switch compartment and the h limit and torque switches was performed at the conclusion of the accident simulation. 9.

) 7) ) 7 ,, i f kH N S pecified Accident Profile Tempe ra tu re Take Insulation og readings and operate Valve Control A i y F F l' II l' l.' 300 OF 300 F 70 ps19 70 psig l 25b F 8 I I 1: l I l 3 I l l 30 psig 8 i 200 F i y l l 8 8 10 ps19 l l 1 i i I I I 8 l 1 l l l l 8 l l I I I I ~ J i t i t i l I l i I i i i I I I 8 I I t 8 g I I I l i i w ,5 + 18 i e j j 8 l8 5 Time 10sec 30 meu 25 ha 2.5 ha 3hs -e7r lu 24 ha. 4"'Dny it ' ony 30*' Day + 10.Sec

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+Z.o eC f 26 5cc s ea O Figure 5 I

FWR Qualification 3.6 Post LOCA Load Cycling Test Similar to that performed at pre-test mechanical aging, [ the unit was cycled for a total of 794 cycles (o~he close ? & one open stroke percycle) at room ambient conditions jf (data supplied in Appendix B). 3.7 Final Inspection A complete physical inspection of the test samples was made after the completion of the Post LOCA Load Cycling to observe the conditions of the actuator. 4.0 Test Results 4.1 Mechanical Aging The unit was initally tested on 7 June 1974 and a thrust output of 20,162 lbs. was obtained at a torgue switch setting of 1-3/4. (This value is an average t. 24 readings.) The unit remained on the test stand and was automatically cycled at room ambient conditions. The cycling test was performed from 7 June 1974 to 10 June 1974 for a total of 1208 cycles consisting of one p torque switch closure in each cycle. T The load was measured after the completion of the mechan-ical aging and an average of 10 readings produced a thrust output of 19,920 lbs. 11.

PWR Qualification f (% The test data obtained is presented in Appendix B. 4.2 Seismic Qualification The Seismic Qualification was performed a't Lockheed f' E Electronics Environmental Laboratory on 12 June 1974. E The data recorded is presented in Lockheed test Re-port No. 3521-4811. (Appendix D.) The thrust load was not monitored during seismic testing; however, thrust readings taken after seismic and radiation, 19,350, average of three readings, was within three (3) percent of the post inechanical aging value. The output characteristics did not change during seismic /*' testing or irradiation. The valve actuator and its limit and torque switch functioned during seismic testing. 4.3 Radiation Aging & Accident Exposure The exposure to radiation of the Test Unit was per-formed on 18 July 1974 at Isomedix Corporation. A total dose of 204 Megarads was used. A Test Certi-fication may be found in Appendix C. ? u 4.4 Accident Environmental Simulation Test Results The LOCA Test was performed at Limitorques' Enviro- % g% mental Test Facility. The environmental test was started 22 August 1974 and completed 21 September 1974. 12.

FWR Qualification 7"s 4.4.1 Temperature and Pres =ure Profile 4CW I Theprofilespecifiedinparagraph3.4.{ofthis r report was closely followed as evidenced in Figure C 6. The transient data was obtained by means of the strip chart recorder. At the transient time of ten (10) seconds, the temperature was a temperature with-o in 91% of the specified temperature (300 F.) A o temperature of 300 F was reached in 15.2 seconds. The second transient closely approximated the first o reaching a temperature of 300 F in 13.8 seconds. 74, Copies of the actu,al strip chart data are presented in Figures 7 & 8. After the transient and a dwell of 30 minutes at o 300 F, the test ambient was brought to a stable o condition of 250 F and 30 psig. The actual temp-erature conditions were within minus 2% and plus 6% of specified temperature and the pressure con-ditions were within plus or minus 3.5%. These f conditions were maintained for the balance of four (4) days. f. mg At a test time of 96.1 hours (approx. 4 days) the ,p o test ambient was lowered to 200 F and 10 psig. The chamber was maintained at these conditions by means 13.

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PWR Qualification ( (% i of strip heaters and air injection through a pressure controlled solenoid valve. On de stability b } was reached, the ambient was maintained yithin plus r s E 0% and minus 4% of specified temperature and plus s. Y 10% and minus 0% of specified pressure. 4.4.2 Chemical Spray Delivery The chemical mixture (per Table 1 of IEEE Std. 382-page 12) was prepared prior to start of the LOCA test and pH values measured. Tank No. 1 had a pH of 10.9 after initial mixing. Tank No. 2 had a pH of 10.5 after initial mixing. The pH was moni-O tored on a sample taken from Tank No. 1 at a test time of 0.1 hours (pH=ll.1) and after 4.4 hours (pH=ll.1). A sample of Tank No. 2 taken at 24 hours had a pH reading of 10.5. The chemical flow was maintained at 0.6 gal / min in each spray manifold or an overall flow rate of 1.2 gal / min. A check was made of the average flow rate by recording the total amount of chemical I solution used in a given period of time. These average flow rates agreed with the recorded in-gma stantaneous flow rates. , f~ 17.

PWR Qualification 4.4.3 Chamber Humidity /* The relative humidity of the chamber was main-I tained at 100 percent by the periodic i ection c of steam and by maintaining the vapor condensate if at the bottom of the chamber at the same tem-Y perature as the air / vapor mixture. The content of air in the air vapor mixture was minimized by venting the chamber during the thermal tran-sients. 4.4.4 Insulation Resistance Measurements Insulation resistance measurements to ground were f**f% made periodically on the power and control leads of the Test Unit prior to operating the valve actuator (see Table II.) 4.4.5 Operator Cycling Data The test unit functioned without problems through-out the entire test. It is worthy to mention that during the final operational cycle (719.1 hours) the close indicating light exhibited a very dim 1 glow when it should have been extinguished. This phenomena was noticed only on the "close" light circuit and no other indicating lights or circuits b,c 18.

.} } 8] TABLE II Insulation Resistance of Power and Control Leads premmtf (All resistances are in Megohms except where a K ind icates Kilo-ohms) (all measurements made to ground) MOTOR LEADS CONTROL CIRCUIT LEADS g Test I 'p-l T-2 T-3 CL-1 61 71 41 43A 43B 43C 45A 45B 51 53A 53B 53C SSA SSB

  • O 400 400 4DO 180 180 180 2000 180 180 180 180 180 180 190 180 100 180 180 0.15 160K 160K 160K 300K 400K 400K 40.0 400K 400K 400K 400K 400K 400K 400K 400K 400K 400K 400K O.5 120K 120K 120K 200K 280F 280K 5.0 280K -280K 280K 280K 280K 280K 280K 280K 200K 200K 280K 3.9 100K 100K 100K 2.0 2.0 2.0 6.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 4.2 SOK SOK SOK 400K 400K 400K 2.4 400K 400K 400K 400K 400K 400K 400K 400K 400K 400K 400K 95.5 80K 80K 80K 2.0K 2.0K 3.0K 40K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 2.0K 334.9 60K 60K 60K 1.5K 1.5K 2.0K 5.0K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 1.5K 719.1 60K 60K 60K 2.0K 2.OK 3.0K 5.0K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K 1.7K

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PWR Qualification exhibited these characteristics. Subsequent in-I' vestigation concluded that the current flow through this light to duplicate thedimglowwashinsignifi-P f cant and coupled with its occurrence in the final t $b-hour of a 30 day test did not constitute a mal-g- function. The megger readings diminished during the environ-mental test and the current & power requirements did increase slightly as the test in the environ-mental chamber continued; however, this had no effect on the actuator performance. The stroke time remained constant throughout the test. D r Also a slight variation in the measured output thrust was noted and was attributed to a change in stem efficiency rather than actuator output torque change. It was noted that during periods of non-operation, the thrust tended to become lower, whereas during periods of frequent operat-ions, the thrust increased. Probably, the ambient temperature & moisture effected the lubricity of the lubricant used on the stem. A summary of the cycling data is presented in Table III. bn 20.

a 3 o 7 7 ) TAllLE III VALVE ACTIRTOR CYCLING DATA h ypnswf n Time Potential OPEN STROKE CLOSE STROKE After (volta) Run Current c Run Current E Power y Start ( k no) M (Amos) o (Watt a) 4 tn $$ bg Y-2 MN7 O $0 $fd T-1 W1 S2

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    • O 490 495 490 4.6 4.8 4.6 620 42 4.G 4.8 4.4 5.0 620 1350 42 19,375

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PWR Qualification 4.5 Post LOCA Inspection P*I' The post LOCA Inspection was performed 21 September Photographs 1974 after opening the test chamber. W were taken of the test unit with the limit swi tch kp. compartment cover in place (see Figure,9). Externally, f the Test Unit was clean looking with no unusual de-posits. The limit switch compartment had approxi-mately one-eighth (1/8) of an inch of condensate in the bottom of the compartment. Both the limit and torque switches were clean and functioned without mechanical difficulties. The D motor lead protective sleeving was split in several r areas: however, no damage was noted to the motor lead insulation. 4.6 Post LOCA Load Cycling The post LOCA Load Cycling was performed by the Limitorque Test Laboratory from 30 September 1974 to 4 October 1974. The thrust output of the Tnst Unit was measured prior to the start of the load cycling. The thrust I output was found to be 16,392 (an average of 6 readings). This was accomplished at the same torque C 22.

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PWR Qualification switch setting (1-3/4) as that used throughout the test. I E.- } The torque output of the actuator as controlled by 1 i the torque switch remains constant with the same [ torque switch setting, however, the thrust monitor in the test stem depends upon several factors in-cluding the efficiency of the acme threads. The lower thrust output monitored af ter the unit was brought to room temperature was attributed to a degredation of stem efficiency as a result of corrosion of the steel etem and deposition of for-f'gg eign materials from.the exposure to the steam and chemical spray and not attributable to changes in the torque switch operating train or reduction in the torque output of the actuator. The effect of the corrosion was most noticeable after the stem was exposed to room ambient con-ditions for several hours. After the completion of the 794 cycles, the thrust monitored returned to its original value indicating the repeated cy-cling had removed the corrosive deposits in the stem thread area. The cycling data and thrust O ~' / reading are presented in Appendix B. 24.

PWR Qualification S ("% A Base Test motor which experienced all the en-vironmental conditions was installed on the test e, actuator after the planned post LOCA cycling to obtain cyclic information on the base motor and 1~ provide additional load cycling on the test unit. The SMB-0 Actuator (with the base test motor) was cycled for an additional 2184 cycles. The SMB-0 Actuator functioned without difficulty throughout the additional 2184 cycles. A summary of the load cycles accumulated on the /"N test unit is as follows: Pretest Mechanical Aging........... 1208 cycles LOCA Testing cycles 9 cycles Post LOCA Load cycling.............. 794 cycles Base Test Motor cycling............ 2184 cycles TOTAL 4195 cycles P 25.

FW'R Qualification 4.7 Final Inspection and Dismantling (' a 4.7.1 Motor Inspection and Dismantling' ) The motor (used with the test unit during E f LOCA test) mounted on the Test Unit was h j. removed from the SMB valve actuator and dismantled for inspection. The inspect-ion was performed on 21 November 1974 with representatives from Reliance Electric Com-pany in attendance. The rotor turned freely prior to dismant-ling the motor. The stator and rotor showed f', little evidence of corrosive build-up and no evidence of physical damage. The end bell was particularly clean with little evi-dence of water. The bearing lubricant was moist and the bearing turned freely. 4.7.2 Valve Control Inspection and Dismantling The SMB-0-40 Valve Actuator was completely dismantled for inspection on 22 November 1974. Photographs of the valve actuator components are presented in Figure 10. fg The torque switch and limit switch were re-P moved from the SM3-0 Valve Actuator and the 26.

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PWR Qualification following observations were made: a.) The torque raitch and limit switches worked freely. [ } b.) The torque switch and limit raitch 7 pinions both showed signs of lubrication. br The grease in the main housing and the handwheel clutch compartment was dark in color but maintained its lubricity. A slight amount of separation of the grease was noted. The O-Ring and bearings seemed in good condition with no wear noted. 5.0 Conclusion The Limitorque Valve Actuator SMB-0-40 was subjected to a O qualification test consisting of a 30-day exposure to a steam chemical environment, including two temperature & pressure transients from 120 degrees F to 300 degrees F in approximately 10 seconds. Prior to environmental testing, the motor was heat aged, the unit was mechani-cally tested and subjected to gamma ray irradiation. The unit was cycled with simulated valve seating loads during environmental testing at elevated temperatures and pres-sures and after environmental test was additionally.cy-cled with a simulated valve seating load. D 28.

PWR Qualification Since the unit performed satisfactorily, throughout the Yr M test, it is concluded this test qualifies similar Limitorque i Valve Actuators for use in a PWR containment chamber where y. environmental conditions depicted by Table I in IEEE i [ Std. 382 '72' are encountered. re N 29.

PWR Qualification V ) b i 7 E C~ [ APPEt: DIX A Relianco Electric Company - Cartificate of Comp 1. ianca 30.

g RELIANCE etecrnic coupany C CERTIFICATE OF COMPLIANCE i h ir

Limitorque Corporation
3114 Woodall Road

$ Lynchburg, Virginia 24502 T L d [C %,%8/p8 ) 4 5 EQUIPMENT: Electric Motor

REFERENCE:

Purchase Order No. 600426-C FILE: Sales Order No. 2'L-2670 74A 1 m We ce rt i fy that the equiperent identi fied above has been designed, ranufac-tured, inspected, and/or tested in accordance with the requirements estab-1ished by the following specifications: RCP-242, Limitorque D/S 21-49-001-1 We further certify that the stator was heat aged 100 hours at le0 C. /O M. Q~W h Quali ty Cont rol Depa rtmen t 3 5 5 E E e k "z 31. v a. e 5 *.6 5 i ' 6C AD / ASHT Aeut A. CHiO 44034 / T E LE;wC'.E 215 992175 GE**E A AL CF FICE s / CLE VE L A*.O. C-tO

PWR Qualification V ( APPE!! DIX B 'h i t I-i r INITIAL TORQUE SWITCH SETTING MECHANICAL AGING POST MECHANICAL AGING THRUST MEASUREMENT POST SEISMIC QUALIFICATION AND RADIATION THRUST MEASUREMENT POST ENVIRONMENTAL THRUST MEASUREMENT POST ENVIRONMENTAL LOAD CYCLING POST LOAD CYCLING THRUST MEASUREMENT t 32.

SUMMARY

OF LOAD CYCLING DATA Specimen: TEST UNIT Limtorque N.,ve Actuator T y Type: SMB k, 2-Size: O [ Serial No. 199935 Motor si'e 40 ft-lb Y I. D.

  1. 2Y267074AlEZ Instrumentation:

Loed Cell: Capacity 90, 000 pounds Manufacturer BLH Serial No. 7517 Strain Indicator: Manufacturer BLH Type N Serial No. 44360% + INITIAL TOROUE FdITCH SETTING Date: 6/7/74 No. of Readings Torque Switch Setting Thrust Output (pounds) 5 "1" 11,070 5 "1 16,010 24 "I 3/4" 20,162

  • Average of all readings MECHANICAL AGING Date:

6/7/74 to 6/10/74 Definition: One (1) cycle Open Limit actuation to close torque Switch actuation to open limit actuation. Two (?) strokes per cycle. Stroke Time: 54 sec

  • Cycle Time:

1 min. 53 see Duty Cycle: 'RUN' 7 cycle.= - 'OFF' 10 min. Load (Th ru s t) : 70,16' pounde (7A Total No. of Cycles: 1708 33.

SUMMARY

OF LOAD CYCLING DATA (continued) h ( The unit was cycled for mechanical aging on a different load stand than was used in the test and since the stroke)was lenger in this stand, a longer stroke time was obtaipod. 1 5i POST MECIWIICAL AGING THRUST MEASUREMENT Date: 6/10/74 No. of Raadings Torque Switch Satting Thrust Output (pound s) 10 "1 3/4" 19,990 POST SEISMIC QUALIFICATION AND RADIATION THRUST MEASUREMENT Date: 8/19/7 No. of Readings Torque Switch satting Thrust Output ( pound s) 3 "I 3/4" 19,250

  • Average of all readings,

POST ENVIRONMFNTAL TEST THRUST MEASUREMENT Date: 9/30/74 No. of Readings Torque Switch Setting Thrust Output (pounds) 6 "1 3/4" 16,392 Note: The low output thrust readings are a result of poor stem efficiency as a result of. -.iu la t ed deposits on the acme threads of the stem. The thrust measured during the last test point of the environmental test was 21,350 pounds. h I 34.

SUMMARY

OF LOAD CYCLING DATA (continued) V I POST ENVIPONMENTAL LOAD CYCLING Date: 9/30/74 - 10/4/74 1 Definition: One (1) cycle h } Open limit to close torque switch { actuation to open limit. Two -( ?) y strokes per cycle. f Stroke Time: 40 sec Duty Cycle: 'RUN' 7 cylcos - 'OFF' 10 minutes Load (Thru st) : 16,397 at start 19,667 at finish Total No. of Cycles: 794 Note: The increase in thrust output is due to improved stem efficiency. The repeated cycling removed the corrosion in the threaded area of the stem. The load cycling was discontinued during the night and ran during the first shift. POST LOAD CYCLING TH'UST MEASUREMENT Date: 10/4/74 e No. of Readings Torque Switch Satting Thrust Ou tput (pounds) ,3 "I 3/4" 19,667 Note: The output thrust returned to the value recorded after the pre-test mechanical aging. b as.

FWR Qualification ( b I ? E APPE" DIX C Radiation Ev.posure - Isomedix Certificate of performance ? f 36.

p 1 1 e ( ISOMEDIX ) July 19, 1974 I i 1 LMr. W. J. Denkowksi Chief Engineer Limitorque Corporation 181 South Gulph Road King of Prussia, Pa. 19406

Dear Mr. Denkowski:

This will summarize the perimeters pertinent to the irradiation of one valve operator and motor assembly. Identification on the valve operator and motor assembly was: SMB O Valve Control s/n 189835 Reliance 40 lb-ft motor I.D. 2Y267074A1EZ b Units were placed in a co-60 field of lx106. rad per hour, at an air equivalent dose. They were rotated several times during the exposure to achieve a more uniform dose distribution. Total dose received to the centerline of the unit was 204 mrad (air equivalent) with an overdose factor on the edges of the units o f 1. 2. in a slight negative pressure. Irradiation was in air and ambient temperature during irradiation did not exceed 1000F.The temperature of the samples Dosimetry was performed using a Victorcen Model 555 Integrating Dose Rate Meter and Probe. The unit was calibrated on January 15, 1974 by the Victoreen Instrument Company, using Cobalt-60 and Cesium-137 sources whose calibrations are trace-able to the U.S. National Bureau of Standards. A copy of the calibration certificate is available. Confirming dosimetry utilizing a Red Perspex syste.,was also e comp le ted. b loomodix inc. 25 Eastmans Road. Pars;ppany, New Jersey (201)587 4700 Vailleg Accrett: Dott O f fite Oca 17 7, Par sippany. N ew Jerley 0 70 34 CH6CAGO DIVISION * ?s 2 s N.,+ 4 a - vertoa Gro.e. tutaois 60053 (3121 966 1160 37. e

~ Mr. W. J. Denkooski July 19, 1974 I k r Irradiation was completed July 18, 1974 and the units returned tg you under separate cover. 5 g Very truly yours, 'd( fhI.d e George Rs Diet: Manager, Radiation Services GRD:km b 6 0 3:

6 PWR Qualification C ( \\ r g s E e l' APPENDIX D Seismic Qualification - Lockheed Test Report O G 39.

m ( TEST REPORT No. 3521-4811 1i I t i I REPOPsT OF TEST l ON LIMITOROUE CORPORATION SMBO OPERATOR W/ MOTOR (40 FT. LB.) AND MOTOR (25 FT. LB.) REPORT W RIT ER: Y ditis TEST ENGINEER- ~ [ W. A. Black LOCKHEED ELECTRONICS COMPANY, IN C. PLAINFIELD, N EW JERSEY DATE: June 17, 1974 APPROVED BY; W N. Jchn Manager Environ ntal Laboratcry -x x Q. 2

(I 54 TEST REPOGT NO. 3521-49ii 3 PURPOSE OF TEST: To subject the test specimens to the Seismic Test reForence'd in Limitorque Corporation Purchase C,r d e r Number 6004SS dated June ti, 1974 ~ MANUFACTURER: Limitorque Corporation f S114 Woodell Road 9 { f Lynchburg, Virginia 24S02 SPECIMENS TESTEO: (a) SMBO Operator with 40 ft. 16. motor.8/N 189835 (b) Relience 2S Ft. Ib. motor 7 g APPLICABLE DOCUMENTS: Limitorque Corporation Purchase Order Number 6004SS dated June 11, 1974 7 PROJECT NUMBER: 24-8041-3811 e CUANTITY OF SPECIMENS TESTEO: One (1) each SECURITY CLASSIFICATION OF SPECIMENS TESTED: Unclassified i UATE TEST COMPLETEO: June 12, 1974 j TEST CONOUCTED BY: LOCKHEED ELECTRONICS COMPANY, INC. ENVIRONMENTAL LABORATORY DISPCSITION OF 1 SPECIMENS TESTED: Returned to Limitorque Corporation per Lockheed Electronics Company, Incorpo-rated Pocking Slip Number 97449 dated ) June 12, 1974 2 ABSTRACT: The test specimens were subjected to y the Seismic Test referenced in g Limitorque Corporation Purchece Order Number 6004S6 dated June 11, 1974, j This test wee completed with no visible a evidence of external damage or resonances. 1 TEST APPARATUS: Reaction-Type Vibration Machine, LA9 Company Model RVH-72-SOOD, S/N S1401 e S. d 1 m PAGE i OF 7

TEST REPORT h0. 3521-4811 (7"5 TEST APPARATUS: Vibration Pickups, M8 Company Type 124, ( (Continued) S/N 14074 and Type 126, S/N 14006. I Vibration Meter, MB Co peny Model M-6, q S/N 539. 'I Dial-A-Gein Amplifiers, Unholt:-Dickie h Hodel 610M, E. L. Number 463 and Model f 610RM-3G, E. L. Number 464 Accelerometers, Endevco Model 22210, S/N NA94 and FC55. TEST PROCEDURE: The test specimens were secured to the test machine, as shown in Figures 1 through 3, and subjected to the follow-ing Seismic Test in accordance with Limitorque Corporation Purchase Order Number 600456 dated June 11, 1974 1. To determine resonant frequencies, en exploratory scan was performed in each of the three (3) major ~ exes over the Frequency range of 5 to 35 Hz with a maximum input acceleration of 1.0 g's. 20. With no resonant frequencies present, the test speciren was sub-jected to 10 second dwells et the Frequencies speciFied by the Limitorque Corporation represente-tive (see data sheetc) in each exis. The vibration emplitude was mainteined at the maximum controll. eble displacement from 5 Hz to the Frecuency at which 3 g's was attained. The input was then maintained at 3 g's Frcm that Fre-quency up to 34 Hz. Eb. The test specimen was vibrated at 35 Hz et en input level cF G + g's For e ten (10) second dwell. The test specimens were actuated during part 2, and all performance monitoring was performed by and the date retained by Philadelphie Geer Corporation per-sonnel. U b Xa e PAGE 2 QF 7

TEST REPORT NO. 3521-4811 TEST RESULTS: The Vibration Test was completed with no visible evidence of external damage noted to either test ocecimen. There were no resonances detected in ) the three (3) exes of vibration. F BECCMMENDATIONS: None. Data merely submitted. 7 i Test Engineer: / ~ I/ldd W. A. Black 7* U 2 8 w PAGE OF 7

Test Report No. 3521-4911 ? ,jd . ?N

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VlBRATION TEST DATA SHEET Z_ //p ? " * "' " 7l - M'" Axis 6 g'7Y DATE > EXPLORATORY (P,n. j) \\ ARIABLE-f 9EOW.C[ u y H INPUT CH 1 CH 2 INPUT CH 1 Ch 2 0008 E A F TUC 4 g ONCHES) ( 5 h c/u . g /_f .cf g r tNoUR AME-Y E -g g 6 0.c // .c /6 - ceV . C S# .cVf .cv7 H 1 INPUT l CU)ATON i 0.c /7 . e /l. .c/t Y . /c o /c.m s O.c/S ,e / 7 .cJ7 _,cSY , c ic c sjL 9 31. c / f c/7 c/T 10 f.clS ct7 . cin .c s2 . c 52 cA-11 'I eif .c/7 .g/9 e TEST SPECIMEN e 12 03 /5 .o ' 7 6/ 9 .cS/ , L 'A. ,e %- NCMENCLATURE 13 \\\\, c 17 .c/$ c sc / /7] c YCR WlM futW 14 1.c t 7 ,gff cac , t FC , 0.S Y .cS9 15 t.c 17 .c/S ,c;/ / $st /Ja L. PERA h a 16 H.c 17 ci7 . cal C52 .cSV ,C 4 C g, c yg 1T H,ct ? .cty ,c 2/ 1a il, e t 7 .o / 9 . gig ,o Sc , g,/ cg2 SERIAL NO 19 ll.c / 7 .d / f .c ; 'A to lLci7 .ci9 . c *J 2 .tV9 . cSd .L&3 21 .ct 7 _c / 9 T., c 1 1 MANUFACTURER 22 i .c r 7 .c/ 9 e3 .c V$ . cB ._c l y' 23 1 _c t 7 ,c 19 ,c4 3 '. c.LL , c /.9 _ _, c) 3 _ .c V9 . cil os 7 L / mire /;' G c;E (e j2 P. Q 25 li e/7 4/9 c23 26 il. C/ 7 .C /9 c]3 cYS .c TL C6C 27 0 o/7 .( / 9 . c 23 ACC EL E FCM E T ER LOC ATIONS 28 !i. C /7 at / 9 . c ) <./ ,cY$ . C 54 _,_( b.5 CH 1 $ini:' ci' /g 7e g 29 !!. c / 7 .c/f .c 1V CH 2 7g g g g ggy 33 i . c /1 .t / 9 CAV ,c V9 , c SC \\ c6 $ j, C/7 ,c/f . c,1 y' l REMARKS 31 32 Legs . c/1 ( .c.145* .cy8 .c s4 I.c n 33 ! __ujf c /9 5, c>YS 34 \\ ta tj_. c /15 cuYS 35 il c,f f C / 9 $- , ( R VjI~ . CY$ c SG .c 7L 36 li 37 Ja }_ k O/htangt__fm r$n_A a m 39 40 $ r%1 Z$1;NUf_Y12~ } 41

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VlBRATION TEST DATA SHEET Ax:S X /1 X 9 ptpost no 5'I ~ W" i / \\ DATE > (//a/7V l E X PLO R ATORY [p,ig] Y TRIA BLE -4RECttNC(.y 2 d Hr j! P4PU T CH 1 CH 2 INPUT CH 1 CH b y _,f DOUBLE AMFLITUDE j (IN CH ES) 4 5 ,(f_V _,, 0,,/ 7,,,_,,,, o / f ,6 3h . c (/ y ,cji tENDUR ANCE TES{, g y' 6 I ,c7/ 7 . 0 /,i .0 / 6 Hr INPUT DUR AT ON Tj.C/V ,t/C . c /L 3 r" ./co lo Ste 8

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. t /t S .tt7 9 I.C/1 .C/ 7 1/3 to 1.c / 9 ' " ti f ci7 'v/9 . c 9 il ,c fd . C fc 11 1,c/99 e TEST SPECIMENS f.d C-NOM E NCL ATU RE 12 1.0 // f ,c/6 .c Ac 13 i.C/T .C/ V C)l / h it g suf pir rv s' E 14 \\\\, cl S ,c) 5 3 %/ 15 l.C/ 8 _C/f ,c p/ ,cSC ,cS7 e5g / $ o s /5s c yn is Tc R s '6 Ed/7T Jif . C 3 2-w/m c 7 c 12 17 II ( / 7 I .C / f . c,2 'A. 13_j.c/7 p/f .c {g SERIAL NO 19 !!2C / 7 .C/f .cl3 20 il.c e 7 .cif . C.2 3 _.c 4 . c iV 0 6.;t. 21 jcf7 ,c f 5 _c},3 M ANUF ACTUR ER 22 ll,cf7 ,c /9 eJ3 23 Il.c/7 .C/ 9 . c 13 5. $/m/TCSSUE(/ 24 \\ ,cr 7 .l/ 9 cs LIL #- 25 l c/7 . c i </ e;y c c/ 7 - _ c fi .C 6 6 26 ll_c /_6 l .C i f .c J V 27 {l,cf 4 f ,C/9 ,p q $ ACC ELE ROM ET E R LOC ATIONS 28 ll } ll i . 0/ 9 .C)$ CH 1 (fris,2 sF /77 ; s g 4 29 '\\. C/ d 'I .0/ f f . C) *i CH 2 Qig g p g g gr-.( yJD ci;o_ .cy .cu7 .cnG .c72 30 31 II,c / d .c/f$ , c.; (. REVARKS 32 i C ll 4-/95 c_2 ] 13 I L.Ll ,Ci?5 _ G) T 34 ll c /d .C /9 6 c2& 35 p, c ff= .c/f5 , cyp __ ce/7 . c i6 . C fr 6 36 ll 37 ij 33 il l 39 il cuna:naa:ajoa "0 N h.1-h.a::.oL h 2 1-41 ll } 42 43 ll k 44 45 !l 46 !l h 47 TEST ENG NEER 43 N 5 [ 7 RES _d 6N Hr g 7 FORM LEC 9228

VlBRATION TEST DATA SHEET g,,5 } jyt, RE %R T NO}f"2_j - y gj t l E XPLOR A TOR hy v /,R I A BL E4 EW ES.Cf., y 3 DATE > 4// 2/7 V H {l INPUT CH 1 CH 2 INPUT CH t CH 2 NOTE RECCRDED DATA 15 DOUBLE AurttiUDE j 4 (INCH ES) 5 Lfd ,C / 6 ,c/c ENDUR ANCE TEST (g 6 11. o c 9 .c i / .C / % , d il , Oy f 631 Hz / IN PU T CURATCN + 7 %.ci 3 .t/7 ,C e a y ,fu ,o m, e i _ cy .c f 7 .c / y 9 > (ti _.C / 7 . c 1 $" 10 'n, c / f f .c/7 a _/ 6 c S/ , c 4/ f . c '/ & c il._c/'6 4/7 .c /6 eTEST SP E CIM E N e 11 12 li e /g 3. .c f 7 .c/r NCMENCLATURE i[g,/7 .c / ~/ .p / 7 /. /n o 7c/T sk/ E/rTc d C 13 LQ/1 ,C / 9 _ci? 15 \\\\.C/1 C/$ ,Ci7S , o49 .c6) . 0 'f 7~ C i'E# A I' A t- $ n1 BC 16 LC /7 . L_/_f c/S m/ ntc Tc A' il ll _ cf_7 .C / V .c/ T 18 ] c/7 2_/ F .c /y SERIAL NO 19 il t/7 c/S . c / 9.V 20 LCD _Ct Si.c/9 ,C W .CS A . cSC 1 J/7 .u/(I_ _c/9 M ANUF ACTURER 22 ll g / 7 , gj f 'f ,c f pr 23 jQ'/7 g,g ,y 2* Lc/7 ._c ! (_. , clC .c Y & .cSV ,o %. Li/ni M A C u E (cA R \\! ,G / 9 C -Is c y 25 [j 11 26 gl7 ,c / 9 (;c 27 ll g f 7 ,c/9 , c ;4[ ACC E L E RC M ET E R LOC ATICNS 25 llA!7 .,C / 5 ij} / CH 1 rc r er sr

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PdR Qualification V t 1 ?. I r APPENDIX E Figure 1 Teet Chamber Figure.2 Steam Generator ~ Figure 3 Control and Instrumentation Panel c 40.

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PWR Qualification V \\ APPENDIX F Figure 4 Schematic Instrumentation Tabls I Summary of Instruments used for Data Acquisition m @( 04.

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= ae n o e c. c: o U e MEASURING SYSTEM P o P E YE N O 6 a Q E 'C c: E ~ a 4 E$ 3 Indicator Signal X-Ducer Monitoring U Se Conditioner Point u 9 m u Z- = a 1* Feb. Feb. ttultipoint 1 ll3 T. C. -J ( ')) Chamber Amb. 1974 1975 Temperature 2 2A T. C. -J ( ?) Test Unit u= Recorder 3 3B T. C. -J ( ? ) L.S. Comp p Type J T. C. 4 4B T. C. -J ( 2) Chamber Amb. 2 5 Room Amb. E yoneywell 6 Shorted y stodel No. 7,10 5 T. C.-J Condensate E A153x80-c-9,11 6 T. C.-J Press x-Dd? t II-W6-65 9,12 7 T. C.-J Press x-Dh3 i Serial No. 13,15,17 8 T. C.-J Press x-DE4 l Tll806-83004 14,16,18 9 T. C.-J Press x Dal C= 19,21,23 10 T. C.-J H O inp5t 2 [ 20,?2,24 11 T. C.-J H 0 output 7 i3 2* i Strip Chart 1 Amplif. Press x-Dul Chamber An,b. Mar. Sepq w e Recorder 2 Press x-Du? Test Unit 1974 1974 c:= 8 Channel 3 Press x-Dd3 L.S. Comp. ma 4 Press x-DE4 Chamber Amb. Gulton 5 T.C. Mod 1 A T.C. -J ( ?) Chamber Amb. TR888 6 'B T. C. -J ( 7 ) Test Unit 7 3A T.C.-J(2) L. S. Comp. E S/N 8 4A T. C. -J (2) Chamber Amb. f 3042802 <c: ra L Note: Amp. TSC 801 b T.C. Mod. TSC 500J e-

TABLE I (continued) SU?OtARY OF DATA ACQUISITION SYSTEM

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s. TABLE I (continued) SU.'O!ARY OF DATA ACQUISITION SYSTEM uce m 2 2 ec w O O E -- 6 o s ou u n b b k o r< 5{ [ Measuring System me Me g j$ na a oa a m EO a a Signal X-Ducer Monitoring U U Indicator Conditioner Point e 0 y 1 2 Stopwatch Stroke -00 - 3 x e Time c0 m Hever S/N 512406 ) 13 Flow Meters (2) Chemical New 2/74 2/75 Fisher & Porter. Flow n 6 o a j L ttodel S/N ,j 10A1735Y 7309A0574A1 h 10A1735 B 7407A0403Al Ce Le 14 2 Dial Pressure Gages Manifold New D Pressure 2/74 2/75 (2) Wesler Model BA14P ,g Pump Indicator { Pressure ~ 1 Acco Helicoid only m L mu e a 0-200 psig 15 PH Meter [ Comparison PH o f Chem. Acainst Solution an ard -.ee ni .s e 3 o...... e e e i oo Solution c Motor & New j,c, James G. Biddle Control 2/74 2/75 oa =a Leads e Model 21159 'T s L r# e l S/N 7325?1 1

LIMITORQUE CORPORATION veg2ryy g 5114 Woodati Road. Lynchburg. Va 24502 d s't / (P Acmtrist atne Office-804 525-4400 e '.ianuf actunng Piart-604 846-8401 Tele x 9448 liep'y t<. _f U t :.w tcp %. x ' x V.m x Q q g,_ ( D:.19 Wai l'a nn t ri?r 1:~rd ).. q.~, o, ) ~ Ch a'I..t r e. % rth rit r < 'o,1. :;i o. v ... a,,, y l'h on t : :D:, 327-2';l ? July 28, 1978 Duke Power Compan'f P.O. Box 2178 Charlotte, N.C. 28242 Attention: Mr. Milton Hopkins

Subject:

Information Request To Limitorque Concerning Documentation Package For Electrical Camponents On EMO Valves For McGuire Nuclear Station Ref A: -Limitorque Environmental Test Report Index Dated 7-12-76, on Pages E-27 and E-28 of Project 81 Electrical Valve Actuator Information Document O Ref B: dimitorque PWR Test Project #600456 Dated 12-9-75 (Inside Primary Containment) Ref C: A,imitorque Class IE Test Project #600461 Dated 5-23-76 (Outside Primary Containment) Ref D: fLimitorgt e Sum nary Sheet On IEEE 323 and IEEE 382 Nuclear Qualification Data For Safety Related Service Dated 12-15-75. Gentlemen: During our meeting of 6-27-78 we discussed the need to identify operation data and docunentation of it's test basis. The above references "A" through "D" were viewed during the meeting. It was mutually decided that the referenced material met your needs except for the following points: CC: Mr. Jim Crenshaw-Duke Power (continued) P Mr. John Boehme-Duke Power Mr. Harry Gibson-Duke Power O Mr. Chuck Johnson-Duke Power Automated Valve Oper stor's and Jacks for Industr y

.t <a a UMITOROVE CORPORATION Sheet No. 2 /~' l. When were the McGuire operators manufactured? h .e According to the units identified by the Henry Millerysurvey of_Limitorque operators at McGuire, these units were' manufactured between 1973.and 1976.. 2. Where testing was performed with a Reliance motor on the actuator, how do you accomodate the motor manufactured by Electric Apparatus and Peerless in the qualifications? All motors are manufactured to electrical and mechanical designs originated by Limitorque Corporation. All motors, regardless of manufacturer, are produced to the same design stress and design tolerance standards. A design family. 3. What was the system used to seal the power wiring at the entrance to the operator during the test projects 600456 and 600461? The connection particulars are described in each report. Pages 7 and 23 on 600456 and Pages 4 and 5 of Appendix IV on 6 0 0 4 6 1. n..,,,, Due to the construction cf the environmental test chamber, it proves necessary to protect the control and power wiring from mechanical abrasion by use of flexible tubing and then to use pressure fittings at the test chamber wall to contain the environment. This system is not used to seal the wiring at the actuator, but merely to adapt the actuator to the test facility. Recognizing the field difficulties that would be incurred if our containment actuators depended on being absolutely pressure tight to survive a LOCA or steam line break conditions, we have designed and qualified our units with open draint on the motor that permit the accident environment to enrer the motor and limit switch compartments. Use of solid wire and sealing of the wire at the operator conduit entrances is not necessary but advantageous. The actuator must not become a drain for condensation in the eletrical conduit. L}}

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